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Oklo signs MOU with Standard Nuclear to explore plutonium recycling
Oklo announced that it has signed a memorandum of understanding with Standard Nuclear to explore commercial collaboration on nuclear fuel recycling and advanced fuel manufacturing. According to Oklo, the collaboration with TRISO fuel fabricator Standard Nuclear represents the company’s first third-party offtake pathway for recycled nuclear materials, including surplus U.S. plutonium.
B. A. Pint
Fusion Science and Technology | Volume 52 | Number 4 | November 2007 | Pages 829-833
Technical Paper | First Wall, Blanket, and Shield | doi.org/10.13182/FST07-A1594
Articles are hosted by Taylor and Francis Online.
One proposed U.S. test blanket module (TBM) for ITER uses ferritic-martensitic alloys with both eutectic Pb-Li and He coolants at ~475°C. In order for this blanket concept to operate at higher temperatures (~750°C) for a DEMO-type reactor, several Pb-Li compatibility issues need to be addressed. A SiC/SiC composite flow channel insert is proposed to reduce the steel dissolution rate (and the magnetohydrodynamic pressure drop). Prior capsule testing examined dense, high-purity SiC in Pb-Li at 800°-1200°C and found detectable levels of Si in the Pb-Li after 2,000h at 1100°C and 1,000h at 1200°C. Current capsule experiments are examining several different SiC/SiC composite materials at 1000°C. Another issue involves Pb-Li transport between the first wall and heat exchanger. Aluminide coatings on type 316 stainless steel and Al-containing alloys capable of forming an external alumina scale have been studied in capsule experiments at 700° and 800°C for 1,000h. Model aluminide coatings made by chemical vapor deposition reduced the dissolution rate for 316SS at 800°C by a factor of 50.